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Understanding the Choices The Future Management of Canada’s Used Nuclear Fuel
Understanding the Choices The Future Management of Canada’s Used Nuclear Fuel
Understanding the Choices is the NWMO’s second discussion document, an important milestone in a three-year study (2002-2005) designed to recommend to the Government of Canada an approach to managing Canada’s used nuclear fuel for the long term. The report begins with an examination of the values and priorities of Canadians, and how the NWMO has used this understanding to build a framework to assess and compare management approaches.
INITIAL SCREENING FOR SITING A DEEP GEOLOGICAL REPOSITORY FOR CANADA'S USED NUCLEAR FUEL - English River First Nation, Saskatchewan
INITIAL SCREENING FOR SITING A DEEP GEOLOGICAL REPOSITORY FOR CANADA'S USED NUCLEAR FUEL - English River First Nation, Saskatchewan
On September 13, 2010, the English River First Nation expressed interest in learning more about the Nuclear Waste Management Organization (NWMO) site selection process to find an informed and willing community to host a deep geological repository for Canada’s used nuclear fuel (NWMO, 2010). This report summarizes the findings of an initial screening, conducted by Golder Associates Ltd., to evaluate the potential suitability of thirteen English River First Nation reserve areas against five screening criteria using readily available information.
Options for Developing Public and Stakeholder Engagement for the Storage and Management of Spent Nuclear Fuel (SNF) and High Level Waste (HLW) in the United States
Options for Developing Public and Stakeholder Engagement for the Storage and Management of Spent Nuclear Fuel (SNF) and High Level Waste (HLW) in the United States
This report puts forth a number of options and recommendations for how to engage stakeholders and other members of the public in the storage and management of spent nuclear fuel and high level waste in the United States. The options are generated from a scientific review of existing publications proposing criteria for assessing past efforts to engage publics and stakeholders in decision-making about risky technologies.
Geological Problems in Radioactive Waste Isolation Second Worldwide Review Part 2 Ch 10 - 17
Geological Problems in Radioactive Waste Isolation Second Worldwide Review Part 2 Ch 10 - 17
The first world wide review of the geological problems in radioactive waste isolation was published by Lawrence Berkeley National Laboratory in 1991. This review was a compilation of reports that had been submitted to a workshop held in conjunction with the 28th International Geological Congress that took place July 9-19,1989 in Washington, D.C.
Disposal and Storage of Spent Nuclear Fuel--Finding the Right Balance, A report to Congress and the Secretary of Energy
Disposal and Storage of Spent Nuclear Fuel--Finding the Right Balance, A report to Congress and the Secretary of Energy
The Nuclear Waste Policy Act of 1982, as amended, established a statutory basis<br/>for managing the nation’s civilian (or commercially produced) spent nuclear<br/>fuel. The law established a process for siting, developing, licensing, and constructing<br/>an underground repository for the permanent disposal of that waste.<br/>Utilities were given the primary responsibility for storing spent fuel until it is<br/>accepted by the federal government for disposal at a repository, which originally<br/>was expected to begin operating in 1998.
Geological Problems in Radioactive Waste Isolation Second Worldwide Review Part 3 Ch 18 -27
Geological Problems in Radioactive Waste Isolation Second Worldwide Review Part 3 Ch 18 -27
The first world wide review of the geological problems in radioactive waste isolation was published by Lawrence Berkeley National Laboratory in 1991. This review was a compilation of reports that had been submitted to a workshop held in conjunction with the 28th International Geological Congress that took place July 9-19,1989 in Washington, D.C.
Final 40 CFR 19: Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes
Final 40 CFR 19: Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes
Final 40 CFR 40 Ruling on Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel , High-Level and Transuranic Radioactive Wastes
Report to Congress on the Demonstration of the Interim Storage of Spent Nuclear Fuel from Decommissioned Nuclear Power Reactor Sites
Report to Congress on the Demonstration of the Interim Storage of Spent Nuclear Fuel from Decommissioned Nuclear Power Reactor Sites
This report discusses the status of the commercial spent nuclear fuel (SNF) inventory in the United States, at both decommissioned and operating commercial nuclear power reactor sites; summarizes the contractual arrangement the government and utilities have under the Standard Contract for Disposal of Spent Nuclear Fuel and/or High-Level Radioactive Waste (10 CFR Part 961) (Standard Contract), related litigation, and the financial liabilities resulting from the Department’s delay in performance under these contracts; provides a history of interim storage policy as it relates to commercial SN
Advanced Fuel Cycle Cost Basis
Advanced Fuel Cycle Cost Basis
This report, commissioned by the U.S. Department of Energy (DOE), provides a comprehensive set of cost data supporting a cost analysis for the relative economic comparison of options for use in the Advanced Fuel Cycle Initiative (AFCI) Program. The report describes the AFCI cost basis development process, reference information on AFCI cost modules, a procedure for estimating fuel cycle costs, economic evaluation guidelines, and a discussion on the integration of cost data into economic computer models.
From Integral Experiments to Nuclear Data Improvement
From Integral Experiments to Nuclear Data Improvement
Target accuracy on LWR neutronics parameters is 2 to 5 times lower than the a priori uncertainty (1σ)
due to nuclear data. This paper summarizes the experimental facilities and the integral measurements that are required
for code qualification. The rigorous use of integral information through trend analysis method is described. Trends
on JEF2 data from Keff measurements and P.I.Es are presented. These trends were accounted for in the new JEFF3
evaluations. The role of fundamental experiments, such as worth measurement of separated isotopes, is emphasized.
Spent Nuclear Fuel: Accumulating Quantities at Commercial Reactors Present Storage and Other Challenges
Spent Nuclear Fuel: Accumulating Quantities at Commercial Reactors Present Storage and Other Challenges
The amount of spent fuel stored on-site at commercial nuclear reactors will continue to accumulate—increasing by about 2,000 metric tons per year and likely more than doubling to about 140,000 metric tons—before it can be moved off-site, because storage or disposal facilities may take decades to develop. In examining centralized storage or permanent disposal options, GAO found that new facilities may take from 15 to 40 years before they are ready to begin accepting spent fuel. Once an off-site facility is available, it will take several more decades to ship spent fuel to that facility.
SCALE-4 Analysis of Pressurized Water REactor Critical Configurations: Volume 5 - North Anna Unit 1 Cycle 5
SCALE-4 Analysis of Pressurized Water REactor Critical Configurations: Volume 5 - North Anna Unit 1 Cycle 5
The requirements of ANSI/ANS 8.1 specify that calculational methods for away-from-reactor
(AFR) criticality safety analyses be validated against experimental measurements. If credit for the
negative reactivity of the depleted (or spent) fuel isotopics is desired, it is necessary to benchmark
computational methods against spent fuel critical configurations. This report summarizes a portion
of the ongoing effort to benchmark AFR criticality analysis methods using selected critical
configurations from commercial pressurized-water reactors (PWR).
Evaluation of Burnup Credit for Accommodating PWR Spent Nuclear Fuel in High-capacity Cask Designs
Evaluation of Burnup Credit for Accommodating PWR Spent Nuclear Fuel in High-capacity Cask Designs
This paper presents an evaluation of the amount of burnup credit needed for high-density casks to
transport the current U.S. inventory of commercial spent nuclear fuel (SNF) assemblies. A prototypic
32-assembly cask and the current regulatory guidance were used as bases for this evaluation.
By comparing actual pressurized-water-reactor (PWR) discharge data (i.e., fuel burnup and initial
enrichment specifications for fuel assemblies discharged from U.S. PWRs) with actinide-only-based
PWR Axial Burnup Profile Analysis
PWR Axial Burnup Profile Analysis
Monitored Retrievable Storage Project Plan
Monitored Retrievable Storage Project Plan
The purpose of this document is to describe the Monitored Retrievable Storage (MRS) Project and to establish approved cost and schedule baselines against which overall progress and management effectiveness shall be measured. For the sake of brevity, this Project Plan will be referred to as the Plan throughout this document.
Fast Flux Test Facility (FFTF) Reactor Fuel Criticality Calculations
Fast Flux Test Facility (FFTF) Reactor Fuel Criticality Calculations
The purpose of these calculations is to characterize the criticality safety concerns for the storage of Fast Flux Test Facility (FFTF) nuclear fuel in a Department of Energy spent nuclear fuel (DOE SNF) canister in a co-disposal waste package. These results will be used to support the analysis that will be done to demonstrate concept viability related to use in the Monitored Geologic Repository (MGR) environment.
FEDERAL COMMITMENTS REGARDING USED FUEL AND HIGH-LEVEL WASTES
FEDERAL COMMITMENTS REGARDING USED FUEL AND HIGH-LEVEL WASTES
Isotopic Generation and Confirmation of the BWR Appl. Model
Isotopic Generation and Confirmation of the BWR Appl. Model
The objective of this calculation is to establish an isotopic database to represent commercial spent nuclear fuel (CSNF) from boiling water reactors (BWRs) in criticality analyses performed for the proposed Monitored Geologic Repository at Yucca Mountain, Nevada. Confirmation of the conservatism with respect to criticality in the isotopic concentration values represented by this isotopic database is performed as described in Section 3.5.3.1.2 of the Disposal Criticality Analysis Methodology Topical Report (Reference 7.1).
Advances in Applications of Burnup Credit to Enhance Spent Fuel Transportation, Storage, Reprocessing and Disposition-Proceedings of a Technical Meeting held in London, 29 August-2 September 2006
Advances in Applications of Burnup Credit to Enhance Spent Fuel Transportation, Storage, Reprocessing and Disposition-Proceedings of a Technical Meeting held in London, 29 August-2 September 2006
This publication records the proceedings of a technical meeting organized by the IAEA and
held in London 29 August–2 September 2005 with sixty participants from 18 countries. As
indicated in the title, the objective of this meeting was to provide a forum for exchange of
technical information on spent fuel burnup credit applications and thereby compile state-ofthe-
art information on technical advances related to spent fuel transportation, storage,
reprocessing and disposition.
slides - Canister Confinement Integrity, Integrated Plan for Addressing Potential Chloride-Induced Stress Corrosion Cracking of Austenitic Stainless Steel Dry Cask Storage System Canisters
slides - Canister Confinement Integrity, Integrated Plan for Addressing Potential Chloride-Induced Stress Corrosion Cracking of Austenitic Stainless Steel Dry Cask Storage System Canisters
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Waste Acceptance System Requirements Document, Revision 5, ICN 01
Waste Acceptance System Requirements Document, Revision 5, ICN 01
The purpose of this document is to establish waste acceptance technical requirements for the U.S. Department of Energy’s (DOE) Civilian Radioactive Waste Management System (CRWMS). These requirements and functions consist of two types: (a) internal CRWMS requirements derived from the Civilian Radioactive Waste Management System Requirements Document (CRD) (DOE 2007a) as illustrated in Figure 1, and (b) acceptance criteria imposed by the CRWMS on spent nuclear fuel (SNF) and high-level waste (HLW) delivered into the CRWMS.
Report on Radioactive Waste Ownership and Management of Long-Term Liabilities in EDRAM Member Countries
Report on Radioactive Waste Ownership and Management of Long-Term Liabilities in EDRAM Member Countries
This report has been prepared by an ad-hoc Working Group (WG) formed by ANDRA (France), NUMO (Japan), NAGRA (Switzerland) and ENRESA (Spain) in May 2003, after the EDRAM meeting held in Valencia to study the situation in the different EDRAM member countries regarding the treatment of radioactive waste ownership and management of long-term liabilities.
Program of Research and Development for Management and Disposal of Commercially Generated Radioactive Wastes: Record of Decision
Program of Research and Development for Management and Disposal of Commercially Generated Radioactive Wastes: Record of Decision
This Record of Decision has been prepared pursuant to the Regulations of
the council on Environmental Quality, 40 CFR Part 1805, on the selection of a
strategy for the disposal of commercially-generated radioactive wastes and the
supporting program of research and development.
The United States Department of Energy has decided to (1) adopt a strategy to
develop mined geologic repositories for disposal of commercially-generated
high-level and transuranic radioactive wastes (while continuing to examine
Direct Radiation Dose Consequence Calculation for Category 1 and 2 Event Sequences
Direct Radiation Dose Consequence Calculation for Category 1 and 2 Event Sequences
Performance objectives for the geologic repository operations area through permanent closure in 10 CFR 63.111 identify compliance with regulatory dose limits for workers and members of the public as a design objective. The purpose of this design calculation is to determine direct radiation dose consequences for Category 1 and 2 event sequences. It does not include worker dose assessment for recovery operations following Category 1 event sequences.